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Digital nuclear control rod control system

a control system and control rod technology, applied in nuclear engineering, nuclear elements, greenhouse gas reduction, etc., can solve the problems of reducing the extent of neutron absorption, increasing the rate of nuclear reaction and core power output, and dropping rods

Active Publication Date: 2014-03-11
WESTINGHOUSE ELECTRIC CORP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Benefits of technology

The nuclear control rod control system described in this patent is designed to control the movement of multiple drive rod systems in a nuclear reactor. The system includes a logic unit that coordinates electrical power to the lift coils, moveable grippers, and stationary grippers of the control rod drive systems. The system also includes a moving unit that controls the electrical power to the lift coils in at least two selecting units, which control the movement of control rod assemblies in groups. Each selecting unit controls at least two groups of control rod assemblies, and the moveable grippers and stationary grippers in each control rod assembly move together in a coordinated manner. The system also includes a current regulator controller that monitors and controls the current in each coil and gripper, and a fault protection system that identifies and isolates faults in the power control modules. The selecting units can also energize the moveable and stationary grippers in the same control rod assembly when the lift coils are not energized. Overall, the system provides precise control and monitoring of the movement of the control rod assemblies in a nuclear reactor.

Problems solved by technology

Inserting a control rod further into the core causes more neutrons to be absorbed without contributing to fission in an adjacent fuel rod; and retracting the control rod reduces the extent of neutron absorption and increases the rate of the nuclear reaction and the power output of the core.
These systems have many single failure mechanisms any one of which can lead to dropped rods.
The systems were designed prior to, and do not take advantage of, the capabilities of modern computer-based instrumentation and control equipment.
Furthermore, these systems are costly to manufacture and maintain and an improved rod control system that overcomes these and other limitations is needed.

Method used

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Embodiment Construction

[0045]The control rods 18 as shown in FIG. 1, are attached in clusters 16, referred to as a control rod assemblies, with each cluster being commonly driven by a drive rod 20 disposed in a vertical support housing 24 above the reactor core 14 containing the fuel rod assemblies into which the control rods 18 are advanced or from which the control rods are retracted for variable damping of nuclear flux within the reactor core. The moving parts of the control rod drive mechanism are within the pressure envelope of the reactor and the electromagnetic coils (CRDM) for driving the moveable parts are disposed around and about each of the housings 24 that extends above the reactor.

[0046]FIG. 2 shows a drive rod drive mechanism 40 with the extended portion of the housing 24 partly cut away to show the grippers 42 and 44 that are operable in sequences to engage, lift and / or lower the drive rod 20 when the associated coils 46, 48 and 50 of the drive mechanism 40 are energized in a prescribed se...

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PUM

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Abstract

A digital rod control system that employs separate power modules to energize the respective coils of a magnetic jack control rod drive rod drive system so that two, independently powered grippers can simultaneously support the control rod drive rod when it is not in motion to avoid dropped rods. The basic building block of the system is two or more selecting cabinets which receive multiplex power from at least one moving cabinet and are under the control of a single logic cabinet. Each of the cabinets include monitoring features to confirm the reliability of the system.

Description

CROSS REFERENCE TO RELATED APPLICATIONS[0001]This application claims priority to Provisional Application Ser. No. 61 / 229,460, filed Jul. 29, 2009, entitled DIGITAL ROD CONTROL SYSTEM.BACKGROUND OF THE INVENTION[0002]1. Field of the Invention[0003]This invention relates in general to nuclear reactor control systems and, in particular, to systems for controlling the movement of nuclear control rods into and out of the core of a nuclear reactor.[0004]2. Description of the Prior Art[0005]In a nuclear reactor for power generation, such as a pressurized water reactor, heat is generated by fission of a nuclear fuel such as enriched uranium, and transferred into a coolant flowing through a reactor core. The core contains elongated nuclear fuel rods mounted in proximity with one another in a fuel assembly structure through and over which the coolant flows. The fuel rods are spaced from one another in co-extensive parallel arrays. Some of the neutrons and other atomic particles released durin...

Claims

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Application Information

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Patent Type & Authority Patents(United States)
IPC IPC(8): G21C7/06
CPCG21C7/36G21D3/001G21C7/12Y02E30/39Y02E30/30Y02E30/00G21C7/00
Inventor ROSLUND, CHARLES J.OTTOBRE, LOUIS G.MEIER, CHRISTOPHER P.BAISCH, JONATHAN E.METHA, JAY B.BEDNAR, FRED H.PINAL, ROLOLFO I.
Owner WESTINGHOUSE ELECTRIC CORP